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Volumn , Issue 1366, 2000, Pages 713-724

Creep-fatigue response of 20% CW 316 SS under irradiation at 60 °C

Author keywords

[No Author keywords available]

Indexed keywords

AUSTENITE; CRACK PROPAGATION; CREEP; FATIGUE OF MATERIALS; FATIGUE TESTING; LIFE CYCLE; PROTON IRRADIATION; RADIATION EFFECTS; STRESS ANALYSIS;

EID: 0034475552     PISSN: 10403094     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1520/stp12426s     Document Type: Conference Paper
Times cited : (14)

References (10)
  • 2
    • 0025510114 scopus 로고
    • An Assessment of Tensile, Irradiation Creep, Creep Rupture, and Fatigue Behavior in Austenitic Stainless Steels with Emphasis on Spectral Effects
    • Grossbeck, M. L., Ehrlich, K. and Wassilew, C., "An Assessment of Tensile, Irradiation Creep, Creep Rupture, and Fatigue Behavior in Austenitic Stainless Steels with Emphasis on Spectral Effects," Journal of Nuclear Materials, Vol. 174, 1990, pp. 264-281.
    • (1990) Journal of Nuclear Materials , vol.174 , pp. 264-281
    • Grossbeck, M.L.1    Ehrlich, K.2    Wassilew, C.3
  • 3
    • 0000087255 scopus 로고
    • Computer Simulation of Early-Stage Irradiation Creep
    • Nagakawa, J., Yamamoto, N. and Shiraishi, H., "Computer Simulation of Early-Stage Irradiation Creep," Journal of Nuclear Materials, Vol. 179-181, 1991, pp 986-989.
    • (1991) Journal of Nuclear Materials , vol.179-181 , pp. 986-989
    • Nagakawa, J.1    Yamamoto, N.2    Shiraishi, H.3
  • 4
    • 0008528008 scopus 로고
    • Calculation of Radiation-Induced Creep and Stress Relaxation
    • Nagakawa. J., "Calculation of Radiation-Induced Creep and Stress Relaxation," Journal of Nuclear Materials, Vol. 225, 1995, pp. 1-7.
    • (1995) Journal of Nuclear Materials , vol.225 , pp. 1-7
    • Nagakawa, J.1
  • 5
    • 0028494590 scopus 로고
    • Calculation of Radiation-Induced Stress Relaxation
    • Nagakawa, J., "Calculation of Radiation-Induced Stress Relaxation," Journal of Nuclear Materials, Vol. 212-215, 1994, pp. 541-545.
    • (1994) Journal of Nuclear Materials , vol.212-215 , pp. 541-545
    • Nagakawa, J.1
  • 6
    • 0000543041 scopus 로고
    • Low-Temperature Irradiation Creep of Fusion Reactor Structural Materials
    • Grossbeck, M. L. and Mansur, L. K., "Low-Temperature Irradiation Creep of Fusion Reactor Structural Materials," Journal of Nuclear Materials, Vol. 179-181, 1991, pp. 130-134.
    • (1991) Journal of Nuclear Materials , vol.179-181 , pp. 130-134
    • Grossbeck, M.L.1    Mansur, L.K.2
  • 8
    • 0018466453 scopus 로고
    • Effect of Specimen Thickness on Mechanical Properties of Polycrystalline Aggregates with Various Grain Sizes
    • Miyazaki, S., Shibata, K. and Fujita, H., "Effect of Specimen Thickness on Mechanical Properties of Polycrystalline Aggregates with Various Grain Sizes," Acta Metallurgica, Vol. 27, 1979, pp. 855-862.
    • (1979) Acta Metallurgica , vol.27 , pp. 855-862
    • Miyazaki, S.1    Shibata, K.2    Fujita, H.3
  • 9
    • 0021214619 scopus 로고
    • Fatigue Crack Growth in Thin Section Type 316 Stainless Steel
    • Rickerby, D. G. and Fenici, P., "Fatigue Crack Growth in Thin Section Type 316 Stainless Steel," Engineering Fracture Mechanics, Vol. 19, 1984, pp. 585-599.
    • (1984) Engineering Fracture Mechanics , vol.19 , pp. 585-599
    • Rickerby, D.G.1    Fenici, P.2
  • 10
    • 17144443218 scopus 로고
    • Fatigue Crack Growth in 316 Type Stainless Steel at Temperatures and Displacement Damage Rates Representative for the First Wall Loading
    • Fenici, P. and Suolang, Shi, "Fatigue Crack Growth in 316 Type Stainless Steel at Temperatures and Displacement Damage Rates Representative for The First Wall Loading," Journal of Nuclear Materials, Vol. 191-194, 1992, pp. 1408-1412.
    • (1992) Journal of Nuclear Materials , vol.191-194 , pp. 1408-1412
    • Fenici, P.1    Suolang, S.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.